Sodium Graphite Reactor Quarterly Progress Report For October December 1955 Section A

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Sodium Graphite Reactor Quarterly Progress Report For October December 1955 Section A

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Author :
language : en
Publisher:
Release Date : 1956

Sodium Graphite Reactor Quarterly Progress Report For October December 1955 Section A written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1956 with categories.

An analysis was made of the nuclear parameters for sodium graphite reactor lattices. These parameters include thermal utilization, macroscopic cross sections, thermal diffusion length, and neutron absorption. Results of all calculations are given in graphical form. Test fuel slugs for the SRE were cycled up to 500 times between 100 and 500 deg C at the rate of 2 cycles/hr. Results are tabulated. The centrifugal casting of U alloy fuel slugs is briefly evaluated. Results of the microscopic examination of the extruded ThU breeder fuels are shown. The percent elongation of graphite due to the presence of Na is shown for various temperatures. Results of wear tests on graphite are also tabulated. The behavior of Zr in liquid Na was studied, and weight gains in Zr are summarized. Analog computer studies were continued, and data are included on the temperature effects of the response time of coolant channel Na outlet temperature thermocouples, the effects of continuous rod motion and pump speed changes on the outlet Na temperature and power, and the outlet temperature as a function of scram time. The critical evaluation of B--Ni rods is tabulated. The fuel rod assembly apparatus is described. Fuel rod development is discussed. Cyclograph traces of rods bonded with various Na--K alloys were recorded for rods at room temperature and heated to 450 and 600 deg F. The traces are indicative of uniform bonding. The moderator can fabrication and testing is also discussed. Tests were completed on Freeze Seal No. 2 for the 6-in. oval port Wedgeplug test valve at 450, 850, and 1250 deg F. The temperature gradients from the hot flange face to the end of the seal mechanism for various valve temperature conditions are shown. Sodium leak rates through the valve are tabulated. Progress in the development of a liquid Na level gage is briefly reported. The tubular heater experiment was completed, and the times to raise pipe temperatures from ambient to 350 deg F are tabulated. Designs for a 6-in. Na pump loop are described briefly. A one to 3.5 scale model of a SRE fuel element was constructed to study the effect of side drag on the element during insertion operations at those fuel channels located near the outlet of the upper plenum chamber. The calibration of the SRE fuel element orifices was studied. Control rod lead screw development is discussed. Development of the safety rod system is described. Core tank galling tests are summarized. Experiments to determine the effects of radiation on MoS/ sub 2/ are described. Dose buildup factors for the concretes to be used in the reactor top shield are tabulated. Constants for the quadratic representation of the dose buildup factor and the capture gamma rays from heavy concrete are also tabulated. The sodium pumps and service system are described. The rated cooling capacity of the SRE tetralin evaporative cooler was checked. Results of a study on the effects of NaK temperature on the H content of He are tabulated. (D.E.B.).

Sodium Graphite Reactor Quarterly Progress Report For April June 1955 Section A

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Author :
language : en
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Release Date : 1955

Sodium Graphite Reactor Quarterly Progress Report For April June 1955 Section A written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1955 with categories.

Sodium Graphite Reactor Quarterly Progress Report For October December 1956

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language : en
Publisher:
Release Date : 1957

Sodium Graphite Reactor Quarterly Progress Report For October December 1956 written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1957 with categories.

Reactor Safety

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language : en
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Release Date : 1963

Reactor Safety written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1963 with Nuclear reactors categories.

Sodium Graphite Reactor Quarterly Progress Report For June August 1953

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language : en
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Release Date : 1954

Sodium Graphite Reactor Quarterly Progress Report For June August 1953 written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1954 with categories.

Sodium Graphite Reactor Quarterly Progress Report

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Author :
language : en
Publisher:
Release Date : 1956

Sodium Graphite Reactor Quarterly Progress Report written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1956 with Nuclear engineering categories.

Tid

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language : en
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Release Date : 1957

Tid written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1957 with Energy development categories.

Report Announcement Bulletin Unclassified Reports For Civilian Applications

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Author : U.S. Atomic Energy Commission
language : en
Publisher:
Release Date : 1957

Report Announcement Bulletin Unclassified Reports For Civilian Applications written by U.S. Atomic Energy Commission and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1957 with Nuclear energy categories.

""The U.S. Atomic Energy Commission is conducting a large-scale review of its research and development reports to make as much information as possible available through the Civilian Application Program. Report Announcement Bulletin ; Unclassified Reports For Civilian Applications is being published to announce immediately, the release of newly declassified reports. ...All reports announced in the Bulletin are available from: Office of Technical Services, Department of Commerce, Washington 25, D.C., at the price listed with each title."--P.iii.

Graphite

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language : en
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Release Date : 1959

Graphite written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1959 with Graphite categories.

Sodium Graphite Reactor Quarterly Progress Report For April June 1957

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Author :
language : en
Publisher:
Release Date : 1957

Sodium Graphite Reactor Quarterly Progress Report For April June 1957 written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1957 with categories.